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Journal of the Nuclear Fuel Cycle and Waste Technology最新文献

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Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method 混合法处理核电厂废离子交换树脂
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.65
N. Kamaruzaman, D. Kessel, Chang-Lak Kim
{"title":"Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method","authors":"N. Kamaruzaman, D. Kessel, Chang-Lak Kim","doi":"10.7733/JNFCWT.2018.16.1.65","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.65","url":null,"abstract":",","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"24 1","pages":"65-82"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88801426","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 14
High-temperature Thermal Decomposition of Cs-adsorbed CHA-Cs and CHA-PCFC-Cs Zeolite System, and Sr-adsorbed 4A-Sr and BaA-Sr Zeolite System cs吸附的CHA-Cs和CHA-PCFC-Cs沸石体系以及sr吸附的4A-Sr和BaA-Sr沸石体系的高温热分解
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.49
Eil-Hee Lee, Jimin Kim, Hyung‐Ju Kim, I. Kim, D. Chung, Kwang-Wook Kim, Keunyoung Lee, B. Seo
{"title":"High-temperature Thermal Decomposition of Cs-adsorbed CHA-Cs and CHA-PCFC-Cs Zeolite System, and Sr-adsorbed 4A-Sr and BaA-Sr Zeolite System","authors":"Eil-Hee Lee, Jimin Kim, Hyung‐Ju Kim, I. Kim, D. Chung, Kwang-Wook Kim, Keunyoung Lee, B. Seo","doi":"10.7733/JNFCWT.2018.16.1.49","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.49","url":null,"abstract":"For the immobilization of high-radioactive nuclides such as Cs and Sr by high-temperature thermal decomposition, this study was carried out to investigate the phase transformation with calcined temperature by using TGA (thermogravimetric analysis) and XRD (X-ray diffraction) in the Cs-adsorbed CHA (chabazite zeolite of K type)-Cs and CHA-PCFC (potassium cobalt ferrocyanide)-Cs zeolite system, and Sr-adsorbed 4A-Sr and BaA-Sr zeolite system, respectively. In the case of CHA-Cs zeolite system, the structure of CHA-Cs remained at up to 900°C and recrystallized to pollucite (CsAlSi2O6) at 1,100°C after undergoing amorphous phase at 1,000°C. However, the CHA-CFC-Cs zeolite system retained the CHA-PCFC-Cs structure up to 700°C, but its structure collapsed in 900~1,000°C, and then transformed to amorphous phase, and recrystallized to pollucite at 1,100°C. In the case of 4A-Sr zeolite system, on the other hand, the structure of 4A-Sr maintained up to 700°C and its phase transformed to amorphous at 800°C, and recrystallized to Sr-feldspar (SrAl2Si2O8, hexagonal) at 900°C and to SrAl2Si2O8 (triclinic) at 1,100°C. However, the BaA-Sr zeolite system structure began to break down at below 500°C, and then transformed to amorphous phase in 500~900°C and recrystallized to Ba/Sr-feldspar (coexistence of Ba0.9Sr0.1Al2Si2O8 and Ba0.5Sr0.5Al2Si2O8) at 1,100°C. All of the above zeolite systems recrystallized to mineral phase through the dehydration/(decomposition)→ amorphous → recrystallization with increasing temperature. Although further study of the volatility and leachability of Cs and Sr in the high-temperature thermal decomposition process is required, Cs and Sr adsorbed in each zeolite system are mineralized as pollucite, Sr-feldspar and Ba/Sr-feldspar. Therefore, Cs and Sr seen to be able to completely immobilize in the calcining wasteform/(solidified wasteform).","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"85 1","pages":"49-58"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89033250","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Basis for a Minimalistic Salt Treatment Approach for Pyroprocessing Commercial Nuclear Fuel 热处理商用核燃料的极简盐处理方法的基础
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.1
M. Simpson, Prashant Bagri
{"title":"Basis for a Minimalistic Salt Treatment Approach for Pyroprocessing Commercial Nuclear Fuel","authors":"M. Simpson, Prashant Bagri","doi":"10.7733/JNFCWT.2018.16.1.1","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.1","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"50 1","pages":"1-10"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79208812","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
A Study on the Manufacturing Characteristics and Field Applicability of Engineering-scale Bentonite Buffer Block in a High-level Nuclear Waste Repository 高放废物处置库工程级膨润土缓冲块的制造特性及现场适用性研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/jnfcwt.2018.16.1.123
Jin-Seop Kim, Seok Yoon, W. Cho, Y. Choi, Geon-Young Kim
{"title":"A Study on the Manufacturing Characteristics and Field Applicability of Engineering-scale Bentonite Buffer Block in a High-level Nuclear Waste Repository","authors":"Jin-Seop Kim, Seok Yoon, W. Cho, Y. Choi, Geon-Young Kim","doi":"10.7733/jnfcwt.2018.16.1.123","DOIUrl":"https://doi.org/10.7733/jnfcwt.2018.16.1.123","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"123-136"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74072171","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 7
Tritium and 14 C in the Environment and Nuclear Facilities: Sources and Analytical Methods 环境和核设施中的氚和14c:来源和分析方法
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.11
X. Hou
{"title":"Tritium and 14 C in the Environment and Nuclear Facilities: Sources and Analytical Methods","authors":"X. Hou","doi":"10.7733/JNFCWT.2018.16.1.11","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.11","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"102 1","pages":"11-39"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86899677","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 27
Preparation of Radiological Environmental Impact Assessment for the Decommissioning of Nuclear Power Plant in Korea 韩国核电厂退役放射性环境影响评价的编制
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.107
Sang‐Ho Lee, Hyung-Woo Seo, Chang-Lak Kim
{"title":"Preparation of Radiological Environmental Impact Assessment for the Decommissioning of Nuclear Power Plant in Korea","authors":"Sang‐Ho Lee, Hyung-Woo Seo, Chang-Lak Kim","doi":"10.7733/JNFCWT.2018.16.1.107","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.107","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"20 1","pages":"107-122"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87165742","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 8
Trends in Technology Development for the Treatment of Radioactive Concrete Waste 放射性混凝土废料处理技术发展趋势
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.93
Keunyoung Lee, Maengkyo Oh, Jimin Kim, Eil-Hee Lee, Kim，Ik Soo, Kwang-Wook Kim, D. Chung, B. Seo
{"title":"Trends in Technology Development for the Treatment of Radioactive Concrete Waste","authors":"Keunyoung Lee, Maengkyo Oh, Jimin Kim, Eil-Hee Lee, Kim，Ik Soo, Kwang-Wook Kim, D. Chung, B. Seo","doi":"10.7733/JNFCWT.2018.16.1.93","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.93","url":null,"abstract":"향후 원자력시설 해체 시 막대한 양의 해체 콘크리트 폐기물이 발생할 수 있음을 감안하였을 때, 방사성 콘크리트 폐기물의 최적 처리기술에 대한 면밀한 검토와 향후 기술개발 방향에 대한 논의는 반드시 필요하다. 본 논문에서는 방사성 콘크리트 폐기물의 국내외 발생 사례를 종합해 보고, 처리 대상이 되는 방사성 콘크...","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"93-105"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76725106","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 21
Characteristics of Solidified Cement of Electrokinetically Decontaminated Soil and Concrete Waste 电净化土壤和混凝土废弃物固化水泥特性研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/jnfcwt.2018.16.1.83
D. Koo, Hyun-Hee Sung, Sangbum Hong, B. Seo
{"title":"Characteristics of Solidified Cement of Electrokinetically Decontaminated Soil and Concrete Waste","authors":"D. Koo, Hyun-Hee Sung, Sangbum Hong, B. Seo","doi":"10.7733/jnfcwt.2018.16.1.83","DOIUrl":"https://doi.org/10.7733/jnfcwt.2018.16.1.83","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"79 1","pages":"83-91"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88909012","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
A Basic Study on Separation of U and Nd From LiCl-KCl-UCl 3 -NdCl 3 System licl - kcl - ucl3 -NdCl - 3体系分离U、Nd的基础研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2018-03-31 DOI: 10.7733/JNFCWT.2018.16.1.59
Tackjin Kim, D. Ahn, H. Eun, Sung-Jai Lee
{"title":"A Basic Study on Separation of U and Nd From LiCl-KCl-UCl 3 -NdCl 3 System","authors":"Tackjin Kim, D. Ahn, H. Eun, Sung-Jai Lee","doi":"10.7733/JNFCWT.2018.16.1.59","DOIUrl":"https://doi.org/10.7733/JNFCWT.2018.16.1.59","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"81 1","pages":"59-64"},"PeriodicalIF":0.0,"publicationDate":"2018-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76355803","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Uncertainty Management on Human Intrusion Scenario Assessment of the Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste: Comparative Analysis of RESRAD and GENII 中低放废物近地表处置设施人为入侵情景评估的不确定性管理:RESRAD与GENII的比较分析
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.369
김민성, 홍성욱, 박진백
{"title":"Uncertainty Management on Human Intrusion Scenario Assessment of the Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste: Comparative Analysis of RESRAD and GENII","authors":"김민성, 홍성욱, 박진백","doi":"10.7733/JNFCWT.2017.15.4.369","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.369","url":null,"abstract":"In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation ‘Safety Case Program’ for the Gyeongju LILW disposal facility.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"212 1","pages":"369-380"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76266222","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
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